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Thermo-mechanical Design Considerations for First Wall of A-SSTR2

Plasma Science and Technology 2003年第1期5卷 1651-1660页

作者：何开辉西尾敏 FusionReactorConceptualDesignDivision SouthwesternInstituteofPhysicsChengdu610041China DepartmentofFusionPlasmaResearch NakaFusionResearchEstablishmentJAERI801-1MukoyamaNaka-machiNaka-gunIbaraki-ken311-0193Japan

The finite element analysis and calculation were performed for the blanket first-wall made of SiC/SiC composite material for Advanced Steady-state Tokamak Reactor 2, A-SSTR2, which at present is conceptually designed in Naka Fusion research establishment, JAERI. Comparison analysis and design window were analyzed using the finite element code ADINA 7.4. Through a 2D calculation for various geometrical configurations and sensitive material properties, a fundamental guideline for the first wall and blanket design are established with respect to maximum temperature, thermal and mechanical stress for many configurations. To satisfy hydrodynamic requirement, a4d4 (the dimension of coolant channel is 4 mm x 8 mm, and the distance between neighboring channels is 4 mm) was chosen as a design point for high thermal conductivity up to 50 W/m.K. In order to find a good solution for lower conductivity, more elaborate work should be done in the future. Nonetheless, the outline of design window for a specific structural material is very useful for the future A-SSTR2 first wall design.

关键词： A-SSTR2 tokamak reactor first wall design thermal-mechanical stress

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Radiation loss in a compound plasma system with high and low temperature regions

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Chinese Physics B 2004年第11期13卷 1902-1906页

作者：程发银 TomonoriTakizuka NobuhikoHayashi 石秉仁 SouthwesternInstituteofPhysics Chengdu610041China nakafusionresearchestablishment JapanAtomicEnergyResearchInstituteIbaraki311-01Japan

A code has been developed for calculating the non-coronal radiation of impurity in a compound plasma system which consists of high and low temperature regions. The radiation loss of impurity carbon in this system is calculated and analysed. The cooling rate in this system is smaller than that in a homogeneous plasma system due to the particle exchange between the two regions of the system. The volumetric radiation is much bigger in the low temperature region than in the high temperature region because of the relatively low temperature and high electron density, despite the much smaller volume.

关键词： plasma non-coronal radiation

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Arc Power Limit and Distribution on the Large Negative Ion Source Based on JT-60 NNBI

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Southwestern Institute of Physics Annual Report 2001年第1期 27-30页

作者： LEIGuangjiu N.Umeda M.Kawai T.Yamamoto M.Kuriyama T.Ohga N.Ebisawa T.Yamazaki M.Kusaka K.Kikuchi S.Hikida K.Usui M.Kazawa S.Numazawa K.Mogaki A.Honda F.Satoh S.Norio K.Ooshima nakafusionresearchestablishment JapanAtomicEnergyResearchInstituteNaka-gunIbraraki-ken311-0193Japan 不详

The target of the large negative ion source based on neutral beam injection (N-NBI) is to produce neutral beam current of 22 A and beam power of 10 MW at 500 keV with duration time of 10 s. Since it was successfully operated in 1996, the 5.3 MW neutral beam power at 380 keV with duration time of 3 s has been achieved. In recent years improving and enhancing the beam power are going on. Several reasons such as plasma non-uniformity, higher beam density at the upper region in the beam profile,

关键词：能量限制能量分配负离子中性电子束等离子体

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Study of Toroidal Rotation Velocity in ITB Discharges by CXRS System in JT-60U Tokamak

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Southwestern Institute of Physics Annual Report 2002年第1期 110-113页

作者： LIWei Y.Sakamoto Y.Koide K.Ushigusa 不详 nakafusionresearchestablishment JapanAtomicEnergyResearchInstituteNaka-gunIbaraki-ken311-0193Japan

Internal transport barriers(ITB) have been achieved and studied in different shear (such as positive shear, weak shear and reversed shear) discharges in most of the major tokamak devices. It is normally produced by ap... 详细信息

关键词：螺旋管旋转速度 ITB放电托卡马克自发螺旋流等离子体

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